5:55 PM - 6:10 PM
[2D22] Characterization Study of Candidate Technologies for Nuclear Material Quantification in Fuel Debris at Fukushima Daiichi Nuclear Power Station
(5)Active Gamma Method
Keywords:neutron induced gamma ray spectroscopy, nuclide identification, shielding, fuel debris
In order to contribute to the development of quantitative technology for the nuclear fuel materials in the fuel debris at the Fukushima Daiichi Nuclear Power Station, the neutron induced gamma ray spectroscopy is studied. We designed a measurement system which consists of a canister for the fuel debris, a neutron source, sheelding materials and a detector. By assigining the benchmark model composition for the fuel debris in the canister, the gamma ray pulse height response in the detector is simulated.